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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Hugh K. Clark
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 351-378
Technical Paper | doi.org/10.13182/NSE82-A20279
Articles are hosted by Taylor and Francis Online.
As a contribution to a required review of the American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors, limits for homogeneous 235U systems have been recalculated to confirm their subcriticality or, where there were doubts, to propose more restrictive values. In addition, other limits were calculated to propose for inclusion in the Standard, namely limits for solutions of 235UO2(NO3)2 and limits for solutions of both UO2F2 and UO2NO3)2 that allow credit for the presence of 238U. Limits were also calculated for uranium oxides. The same three methods of calculation were used as in similar work done recently for plutonium systems. The validity of each was established by extensive correlations with pertinent critical experiments.